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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
Hans K. Richards
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 54-61
Technical Paper and Note | Fuel | doi.org/10.13182/NT71-A30947
Articles are hosted by Taylor and Francis Online.
Data are reported from experiments performed to measure thermal expansion of uranium carbide up to the meltin, point, the expansion accompanying the transition from solid to liquid, and thermal expansion in the liquid phase. The thermal expansion of the tantalum carbide crucibles, used to hold the uranium carbide specimens, was also measured. Experiments were performed using a high-temperature, helium-atmosphere, tungsten filament furnace. Compatibility tests showed that tungsten-graphite and tungsten-tantalum carbide pairs fused together at ∼2400°C; tantalum carbide and graphite remained compatible to 2800°C over the time scale necessary for the expansion measurements. Changes in the length of each expansion sample were measured by detecting electrical contact between the sample and a graphite rod. For measurements in which the uranium carbide was molten, a tantalum carbide disk was placed at the end of the graphite rod to prevent attack of the sensing rod by the molten uranium carbide. Melting point of the uranium carbide samples was 2550°C. The average uranium carbide linear thermal expansion from room temperature to the melting point is 17 × 10−1/°C. Volume expansion upon melting of uranium carbide is 11.4%. A provisional linear thermal expansion of 35.2 × 10−1/°C was measured for molten uranium carbide thermal expansion between 2650 and 2740°C.